Report

FZJ-2016-05878

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png The depletion computer code ORIGEN-JUEL-II

Rütten, H.-J. (Corresponding author)FZJ*

1993
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Please use a persistent id in citations: http://hdl.handle.net/2128/12696

Report No.: Juel-2739

Abstract: The ORIGEN-Z-1-11 in its basic calculating method is derived from the ORNL point depletion code ORIGEN. The advanced JÜL-II-version can make use of irradiation-histogram data of fuel batches given in the form of multigroup cross sections and multigroup neutron fluxes, both varying with time during the irradiation period of the fuel. A high flexibility in processing nuclear data enables the user to determine, to which extend he will substitute the nuclear data of the ORIGEN-libraries by his own, externally generated multigroup cross sections. He may decide, how much to go into detail, describing the time-dependent change not only of the height but also of the spectrum of the neutron flux. As results the user may obtain the radioactivity of the fuel, the decay power, hazards of incorporation, y-spectra and neutron sources at any point in time during the in-core irradiation as well as the properties of spent fuel during the periods of fuel storage, obtaining an improved degree of accuracy. The JÜL-II-specific application mode of the code is restricted to nuclear facilities having a thermal neutron spectrum.

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Contributing Institute(s):

1. Publikationen vor 2000 (PRE-2000)

Research Program(s):

1. 899 - ohne Topic (POF3-899) (POF3-899)

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Database coverage:

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